ML17252A249
| ML17252A249 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 11/30/1976 |
| From: | Stephenson B Commonwealth Edison Co |
| To: | James Keppler NRC/RGN-III |
| References | |
| 50-249/1976-31 BBS Ltr. #76-834 | |
| Download: ML17252A249 (3) | |
Text
- Commonwea9Edison Dresden Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 BBS.Ltr. #76~834 ae~urt~'* o k t
. relgµ,,~JlJY-'"- oc e.File November 30, 1976 Mr. James G. Keppler, Regional Director Directorate of Regulatory Operations - Region I I I U *. S. Nuclear Regulatory Commission 799.* Roos eve 1 t Road G.,l t;n E-11 yn, I 11 i no i s 6013 7 I
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- 1 Enclosed please find Reportable Occurrence report number 50-249/1976-31.
This report is being submitted to your office in accordance with the Dresde~
Nu~lear Power Statton Technical Specifications, Section 6.6.B.
,/
(:,.*. /
BBS :jo Enclosure cc:
Director of Inspection & Enforcement
. ' ~-' st~~~~
St~tion Superintend~nt Dresden Nuclear Power Station f '
Director of Management Information & Progr.am Contro.J-File/NRC
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LICENSEE E\\' ~NT REPORT 1.11 I I
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[.SE PRINT ALL ~EQUIRED iNFOAMATICN)
. C?NTROL BLOCK: I 1
LICENSEE t
NAME
@12] I II LID 17< I Sl3 I LICENSE NUMBER IO IO 1-IO IO IOIOIOl-IOIQJ LICENSE EVENT TYPE TYPE 1 tt 1,. 1 ' 1 ' 1 / r *1 o I 3 1
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25 26 30 31 32 CATEGORY
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58 REPORT REPORT TYPE SOURCE lbJ lbJ 59 60 DOCKET NUMBER 101s101~101114191 61 68 EVENT CATE 11111011 171'1 69 74 REPORT DATE 11111310171~1 75
. 80' EVENT DESCRIPTION
. * (filg] I DUR.ING-REEUEJ..ING-OUTAGE bPCAL. LEAK-RATE TESTING-1 TH£ VOLUfYI£ I
7 8 9 80 fol31 I BOUJJD£D BY A BLINI> FL.ftNG.£
!!ND RTZACTOR.
HEAD GOO~/N(;. JN80AR1> I 7.. 8 9
- 80.
lol4l I 1soJ..ATION GH£.CI< VA.LVS 3-,;2.05- ';;.-7
£x:H1BrrED 11 bAI<. RATE OF I
7. 8 9 80 iols!J11PPROXl!>'1ATE:Ly 3~0 SCFH (TECH SPEC J...l!!uT: 2.'f. 3g1 SCFH). SINGE TH£J lolsl*. flLJND Fl-ANG-EE. EXHJBrTED NO DETECT. BL£ /....EA TH£ AS -FOUND..
- 7 8 s PRME (ssc. ATTllP/£.D SHEET.
so SYSTEM. \\:
CAUSE COMPONENT COMPONENT COOE CODE COMPONENT COOE SUPPLIER MANUFACTURER VDLATION
- 7. 8 9 10 11 12 17 43 44 47.
LiJ 48 CAUSE DESCRIPTION lolsl I nu~* VALVE: L£Al<AG: WA~ APPARENTLY CAU5£D 'BY 7
8 9 VtRT tN THE SE.BTrNC.-1 ::
80..
lolsl IAREA AND ON I~ J)f5;C... PIVOT PIN./71-1£ VALV£ WAS Gl-£ANED. 11.N.D TH£.
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1 IT1§J I S£tmN6-SURFACE WA-5: LJtPPEJ). SUGSEQU£NT RET£ST!NG-OF V.A~ \\/£
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B g FACILITY
- METHOD OF (S££ ATT!lcrr-<=J) SH'££T)
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. STATUS
'!!. POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION EEl lHJ Io I o I o I Nil rnJ 7
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10 12 13 44 45 46 FORM OF ACTIVITY CONTENT:
RELEASED
. OF RELEASE AMOUNT OF ACTIVITY
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10 11 44
. LOCATION OF RELEASE Nil 4-5~---~--------..~~~~~~~~~~~a~o:*
PERSONNEL EXPOSURES TYPE DESCRIPTION
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PEflS.QNNE_L INJURIES NUMBER.
DESCRIPTION EE IO 10 I 01
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7 8 9 11 12 80 OFFSITE CONSEQUENCES hlsl **
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- a. s 80 LOSS OR DAMAGE 'TO FACILITY
.TYPE
[!E].gj 7
8 9 10 DESCRIPTION
- VA BOL PUBLICITY (fil]
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8 9 80 ADDITIONAL FACTORS
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AIA 7
8 9 BO
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7 89 NAME: 'RAN'l>OLPH c. lAJe I DNER 80 PHONE: xT. U5 GPO 891*1587
EVENT DESCRIPTION (Continued) leakage was attrLbuted entirely to leakage through check valve 3-205-2-7.
A second -1 eak-rate test -of the vo 1 ume bounded by the b-1 ind f 1 ange 'and redundant reactor head cooling outbo~rd isolation valve MO 3-205-2-4 established that actual t.hrough-leakage for the penetration was 1.29 SCFH.
Containment integrity, therefore, wps not compromised by_ this failure.
This is the first reported leak-rate test failure for this valve.
(50-249/1976-31)
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CAUSE DESCRIPTION (Continued) 3-205-2-7 yielded a leakage rate of 1.05 SCFH.
Since check valve 205-2-7 has fijnctioned satisfactorily over a period of several years, and since ~edundant va~ve 205-2-4 continues to perform s~tisf~ctorily, testing of this valve on an approximately annual basis should. permit any recurring problem to be id.entified
.in\\, a timely manner.
Valve 3-205-2-7 is* a 2-!-inch Duo-Chek style B check valve, maryufactured by the Mission Valve and Pump Co.
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